Development of transient thermal-hydraulic analysis code for SCO2-cooled reactor coupled with Brayton cycle and its application

H. Ding, D. G. Lu,D. T. Sui

ANNALS OF NUCLEAR ENERGY(2022)

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摘要
Supercritical carbon dioxide (SCO2) direct cycle gas fast reactor system has attracted lots of attention from different institutions worldwide. Most of the research on SCO2-cooled reactors put emphasis on the design and optimization of core parameters, but few on detailed thermal-hydraulic analysis for SCO2-cooled reactors coupled with Brayton cycle. To supplement the lack of research in this area, a pro-gram based on Modelica language is established for transient simulations of SCO2-cooled reactor system. Then, the results of developed Modelica model are compared with code results obtained by GAMMA+, FROBA-SCO2 and SACOS-SCO2, which achieves good agreement. Based on the developed models and codes, thermal-hydraulic characteristics of SCO2-cooled reactor coupled with simple Brayton cycle under the conditions of reactivity insertion accident are studied. According to the validation and transient sim-ulations for different reactivity insertion accidents, Modelica model developed in this paper shows great ability in getting more detailed transient performance of coupled SCO2-cooled reactor system under dif-ferent working conditions. (C) 2022 Published by Elsevier Ltd.
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关键词
Brayton cycle,Reactivity inserted accident,Modelica,Transient simulation
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